IEC TR 62987:2015
(Main)Nuclear power plants - Instrumentation and control systems important to safety - Use of Failure Mode and Effects Analysis (FMEA) and related methods to support the justification of systems
Nuclear power plants - Instrumentation and control systems important to safety - Use of Failure Mode and Effects Analysis (FMEA) and related methods to support the justification of systems
IEC TR 62987:2015(E) provides guidance on nuclear-specific issues when applying failure modes and effects analysis (FMEA) and related methods to instrumentation and control systems important to safety in nuclear power plants. The information in this Technical Report complements, for nuclear power plant applications, the procedure for FMEA in IEC 60812.
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IEC TR 62987 ®
Edition 1.0 2015-09
TECHNICAL
REPORT
colour
inside
Nuclear power plants – Instrumentation and control systems important to safety –
Use of Failure Mode and Effects Analysis (FMEA) and related methods to support
the justification of systems
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IEC TR 62987 ®
Edition 1.0 2015-09
TECHNICAL
REPORT
colour
inside
Nuclear power plants – Instrumentation and control systems important to safety –
Use of Failure Mode and Effects Analysis (FMEA) and related methods to support
the justification of systems
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
ICS 27.120.20 ISBN 978-2-8322-2886-9
– 2 – IEC TR 62987:2015 © IEC 2015
CONTENTS
FOREWORD . 3
INTRODUCTION . 5
1 Scope . 7
2 Normative references . 7
3 Terms and definitions . 8
4 References to FMEA in published standards . 8
4.1 General . 8
4.2 IEC standards . 8
4.2.1 IEC 60812 . 8
4.2.2 IEC 61513 . 9
4.2.3 IEC 61226 . 9
4.3 Other standards . 9
4.3.1 General . 9
4.3.2 IEEE Std 7-4.3.2-2003 . 9
4.3.3 ANSI/IEEE Std 352-1987 . 9
4.3.4 IEEE Std 577-2004 . 10
5 Scope of application of FMEA . 10
5.1 Relationships to other methods . 10
5.2 Analysis subjects . 10
5.3 Common cause failure . 10
6 Examples of applications . 11
6.1 General . 11
6.2 Replacement items . 11
6.3 Survey results . 12
7 Industry practice and regulatory relevance . 12
7.1 General . 12
7.2 France . 12
7.2.1 Experience of practice for FMEA records authority (licensing) . 12
7.2.2 Board-level FMEA . 13
7.2.3 System-level FMEA . 14
7.2.4 Subset-level FMEA . 15
7.2.5 Tools to support FMEA . 16
7.2.6 Current research. 17
7.2.7 Dissemination of FMEA practice . 17
7.3 United Kingdom . 18
7.4 United States . 18
8 Conclusions . 19
Annex A (informative) Standardized form used in survey . 20
Bibliography . 21
Figure 1 – Safety case studies including FMEAs . 13
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS – INSTRUMENTATION
AND CONTROL SYSTEMS IMPORTANT TO SAFETY – USE OF
FAILURE MODE AND EFFECTS ANALYSIS (FMEA) AND RELATED
METHODS TO SUPPORT THE JUSTIFICATION OF SYSTEMS
FOREWORD
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The main task of IEC technical committees is to prepare International Standards. However, a
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example "state of the art".
IEC TR 62987, which is a technical report, has been prepared by subcommittee 45A:
Instrumentation, control and electrical systems of nuclear facilities, of IEC technical
committee 45: Nuclear instrumentation.
The text of this technical report is based on the following documents:
Enquiry draft Report on voting
45A/1006/DTR 45A/1028/RVC
Full information on the voting for the approval of this technical report can be found in the
report on voting indicated in the above table.
– 4 – IEC TR 62987:2015 © IEC 2015
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INTRODUCTION
a) Technical background, main issues and organisation of the Technical Report
Failure mode and effects analysis (FMEA) is a qualitative method of reliability analysis
that may be applied to many different types of systems. It is an inductive method of
performing system reliability or safety analysis from a low to a high level (IEC 60812).
There is a need to provide guidance on nuclear-specific issues, for example common
cause failure and meeting the single failure criteria, when applying failure mode and
effects analysis (FMEA) and related methods to instrumentation and control systems
important to safety in nuclear power plants. The information gathered in the development
of this technical report was used to determine if the topic can be standardised. If a positive
conclusion was reached the intent was to produce a s
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